Process for recovery of palladium from nuclear fuel reprocessing wastes
Patent
·
OSTI ID:863993
- Oak Ridge, TN
- Wartburg, TN
Palladium is selectively removed from spent nuclear fuel reprocessing waste by adding sugar to a strong nitric acid solution of the waste to partially denitrate the solution and cause formation of an insoluble palladium compound. The process includes the steps of: (a) adjusting the nitric acid content of the starting solution to about 10 M, (b) adding 50% sucrose solution in an amount sufficient to effect the precipitation of the palladium compound, (c) heating the solution at reflux temperature until precipitation is complete, and (d) centrifuging the solution to separate the precipitated palladium compound from the supernatant liquid.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Assignee:
- United States of America as represented by United States (Washington, DC)
- Patent Number(s):
- US 4290967
- OSTI ID:
- 863993
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
process
recovery
palladium
nuclear
fuel
reprocessing
wastes
selectively
removed
spent
waste
adding
sugar
strong
nitric
acid
solution
partially
denitrate
formation
insoluble
compound
steps
adjusting
content
starting
10
50
sucrose
amount
sufficient
effect
precipitation
heating
reflux
temperature
complete
centrifuging
separate
precipitated
supernatant
liquid
reprocessing waste
supernatant liquid
acid solution
nitric acid
nuclear fuel
spent nuclear
amount sufficient
selectively removed
fuel reprocessing
selectively remove
strong nitric
reprocessing wastes
processing waste
/999/423/976/
recovery
palladium
nuclear
fuel
reprocessing
wastes
selectively
removed
spent
waste
adding
sugar
strong
nitric
acid
solution
partially
denitrate
formation
insoluble
compound
steps
adjusting
content
starting
10
50
sucrose
amount
sufficient
effect
precipitation
heating
reflux
temperature
complete
centrifuging
separate
precipitated
supernatant
liquid
reprocessing waste
supernatant liquid
acid solution
nitric acid
nuclear fuel
spent nuclear
amount sufficient
selectively removed
fuel reprocessing
selectively remove
strong nitric
reprocessing wastes
processing waste
/999/423/976/